LER 90-007-00:on 900418,ruptured Seal on Outer Door of Upper Containment Airlock Occurred Causing Loss of Containment Integrity.Caused by Inadequate Communications & Equipment Failure.Seal on Outer Door ReplacedML20043A780 |
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Perry |
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05/18/1990 |
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Hegrat H CENTERIOR ENERGY |
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ML20043A705 |
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References |
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LER-90-007, LER-90-7, NUDOCS 9005230115 |
Download: ML20043A780 (3) |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18011A5401994-08-10010 August 1994 LER 94-017-00:on 940711,automatic Isolation of RHR Sys Shutdown Cooling Suction Outboard Containment Isolation Valve Occurred Due to Inadequate Work Order.Work Order Process for I&C Work Orders Will Be reviewed.W/940810 Ltr ML20046C5721993-08-0606 August 1993 LER 93-015-00:on 930709,unexpected RRP Fast to Slow Speed Downshift Occurred Due to Failure of Both RRP Suction Temp Rtd.Replaced & Returned RTD to Mfg for Failure Analysis. W/930806 Ltr ML20046B7811993-08-0202 August 1993 LER 93-014-00:on 930703,TS 3.0.3 Entered Due to Failure of Racs Power Supply.Replaced 5 Volt Power Supply in Racs cabinet.W/930802 Ltr ML20045G7201993-07-0808 July 1993 LER 93-013-00:on 930608,control Room HVAC Sys Train a Supply Fan Tripped on Overcurrent,Resulting in Both Sys Trains Being Unavailable.Caused by Motor Winding Insulation Failure.Motor Repaired by mfg.W/930708 Ltr ML20045G2171993-07-0707 July 1993 LER 93-012-00:on 930607,noted That HPCS Initiation Signal Resulted in Auto Start of Div 3 DG & ESW Sys.Caused by Failure of Div 3 Reserve Battery Charger.Procedures Used for Insp & Maint of Battery Being modified.W/930707 Ltr ML20044F2161993-05-19019 May 1993 LER 93-011-00:on 930419,identified That Excessive Strainer Differential Pressure Across RHR Suction Strainers Could Have Compromised Long Term Cooling During LOCA Operation. Caused by Inadequate Program requirements.W/930519 Ltr ML20044B6771993-02-22022 February 1993 LER 93-004-00:on 930121,MOV Testing of Main Steam Line Drain & Bypass Outboard Isolation Valve Indicated That Thrust Less than Design Thrust to Close Valve Under Accident Conditions. Review,Per GL 89-10 in progress.W/930222 Ltr ML20029B6431991-03-0808 March 1991 LER 91-007-00:on 910209,pressure Switch Instrument Drift Caused Automatic Start of Annulus Exhaust Gas Treatment Sys. Caused by Component Failure.Switch Recalibrated to Adjust Setpoints to Proper value.W/910308 Ltr ML20029B0971991-03-0101 March 1991 LER 91-006-00:on 910202,inboard Isolation Valves Closed on RWCU Delta Flow High Signal During Removal of RWCU Filter from Svc.Caused by Personnel Error.Sys Operating Instruction Being revised.W/910301 Ltr ML20029A6451991-02-22022 February 1991 LER 91-005-00:on 910129,discovered That Two Power Supplies Had Excessive Ripple Effect When All Rods Pushbutton Depressed,Resulting in Loss of Scram Accumulator Fault Indication.Caused by Personnel error.W/910222 Ltr ML20029A3321991-02-15015 February 1991 LER 91-004-00:on 910120,three Reactor Water level-high (Level 8) Channels Inoperable Due to Blown Fuse.Caused by Voltage Spike.Circuitry Associated W/Trip Relays Modified. W/910215 Ltr ML20028H7521991-01-25025 January 1991 LER 90-041-00:between 901212 & 28,inoperable Reactor Pressure Vessel Level Instrumentation Channels Resulted in HPCS Sys Being Inoperable & in Tech Spec Violation.Caused by Personnel Error.Memo issued.W/910125 Ltr ML20024F7421990-12-14014 December 1990 LER 90-033-00:on 901120,Train B of Control Room HVAC Sys Actuated Unexpectedly in Emergency Recirculation Mode.Caused by Inadequate Instruction.Procedure Revised Re Correct Guidance During Loss of Power to Bus K-1-N ML20024F7411990-12-14014 December 1990 LER 90-032-00:on 901116,disconnecting Wires to Test Relay Contact Resulted in RHR a Shutdown Cooling Sys Isolation. Caused by Procedure Deficiency & Inadequate Instructions. Personnel Trained Re Review of Work Orders ML20028G9181990-09-28028 September 1990 LER 90-020-00:on 900831,maint Activities on Control Room Emergency Recirculation Sys Resulted in Tech Spec Violation & Compromise of Safety Sys.Caused by Program Deficiency. Maint Acitivities & Insp Being revised.W/900928 Ltr ML20044B1021990-07-13013 July 1990 LER 90-013-00:on 900619,discovered That Main Steam Line Radiation Monitor C Inoperable for Greater than Time Allowed by Tech Specs 3.3.1.a & 3.3.1.b.Caused by Personnel Error. Personnel counseled.W/900713 Ltr ML20043H4801990-06-20020 June 1990 LER 90-011-00:on 900521,discovered That Divisional LPCI & LPCS Sys Inoperable in Excess of Tech Spec Action Limits Between 871119-23 & 891218-22.Caused by Procedural Deficiency.Sys Operating Instruction revised.W/900620 Ltr ML20043H5251990-06-20020 June 1990 LER 90-010-00:on 900521,Tech Spec Action Requirements Not Implemented for Inoperable Control Rod Scram Accumulators. Caused by Inadequate Procedures & Malfunctioning Transformer.Analyzer Reset & Leakage monitored.W/900620 Ltr ML20043H3841990-06-18018 June 1990 LER 90-009-00:on 900517,RHR Sys B HX Bypass Valve Failed to Reposition on Demand,Rendering RHR Sys Train Operable for Containment Spray Cooling Mode of Operation.Caused by Failure of Valve Stem Nut.Stem Nut replaced.W/900618 Ltr ML20043E5711990-06-0808 June 1990 LER 89-030-01:on 891125,plant Entered Tech Spec 3.0.3 Due to Two Untrippable Control Rods.Failure of Two Control Rods Caused by Improper Seat Matl in Associated Scram Pilot Solenoid Valves.Instructions revised.W/900608 Ltr ML20043A7801990-05-18018 May 1990 LER 90-007-00:on 900418,ruptured Seal on Outer Door of Upper Containment Airlock Occurred Causing Loss of Containment Integrity.Caused by Inadequate Communications & Equipment Failure.Seal on Outer Door Replaced ML20043A8451990-05-18018 May 1990 LER 90-008-00:on 900420,unexpected Isolation of RWCU Sys Occurred.Caused by Component Failure.Faulty Transmitter Transmitter Identified & Replaced ML20042G7731990-05-11011 May 1990 LER 90-006-00:on 900411,control Room Emergency Recirculation Sys Found to Be Inoperable & Tech Specs 3.0.3 Entered on Three Occasions.Caused by Operator Error & Component Failure,Respectively.Personnel retrained.W/900511 Ltr ML20012D8151990-03-24024 March 1990 LER 90-003-00:on 900222 & 23,discovered That Stroke Time Measurements Not Performed in Both Directions for motor- Operated Valves in safety-related Sys.Caused by Program Deficiency.Procedural Enhancement implemented.W/900323 Ltr ML20011E1861990-02-0202 February 1990 LER 90-001-00:on 900107,reactor Scram Occurred After Improper Transfer of 480-volt Ac Power Supplies Resulted in Total Loss of Feedwater Flow & Power Interruption.Caused by Personnel Error.Operator Counseled & Instructions Revised ML20011E1871990-02-0202 February 1990 LER 90-002-00:on 900107,RCIC Sys Isolated Due to High Differential Temp Signal Detected Across RCIC Room Cooler Following Reactor Scram Due to Loss of Feedwater Flow. Caused by Design Deficiency.Procedures Re Flow Rate Revised ML19354E0961990-01-19019 January 1990 LER 89-032-00:on 891228 & 900105,HPCS Sys Declared Inoperable Due to Inoperability of Div 3 Battery.Caused by Low Pilot Cell Voltage,Cell W/Slow Electrolyte Leak & Blown Power Fuse.Fuse & Hydromotor Pump replaced.W/900119 Ltr ML20005E6851990-01-0505 January 1990 LER 89-031-00:on 891206,08 & 15,RWCU Sys Isolations Occurred.Caused by Design Deficiency & Deficiency in Leak Detection/Differential Flow Circuitry Setpoint &/Or Time Delay.Leak Detection Thermocouples relocated.W/900105 Ltr ML20005E0821989-12-26026 December 1989 LER 89-030-00:on 891125,plant Entered Tech Spec 3.0.3 Due to Two Untrippable Control Rods.Caused by Failure to Return Scram Pilot Valves Used for Rods to Mfg After Recall. Surveillance Instruction revised.W/891226 Ltr ML19354D5991989-12-17017 December 1989 LER 89-029-00:on 891117,heater Bay/Turbine Bldg Vent Gaseous Effluent Particulate & Iodine Samples Not Continuously Collected as Required by Tech Spec 3.3.7.10.Caused by Procedure Deficiency.Procedure revised.W/891217 Ltr ML19325E5901989-11-0303 November 1989 LER 89-028-00:on 891008,concluded That Operation of Fuel Pool Cooling & Cleanup Sys to Upper Containment Pools Caused Containment Vacuum Breaker Actuations.Caused by Unrecognized Sys Interaction.Operating Instruction revised.W/891103 Ltr ML19324B1241989-10-27027 October 1989 LER 89-024-01:on 890723,entry Into Operational Condition 2 Completed W/Suppression Pool Makeup Sys Inoperable & on 890725,vent Valve on Ref Leg Found Open & Uncapped.Caused by Personnel Error.Personnel counseled.W/891027 Ltr ML19325D5121989-10-20020 October 1989 LER 89-027-00:on 890925,loss of Control Power to Emergency Svc Water Sys Pump Discharge Valve a Rendered Sys Inoperable.Caused by Personnel Error Re Jumper Placement. Involved Technicians counseled.W/891020 Ltr ML19325D1581989-10-13013 October 1989 LER 88-025-01:on 880618,reactor Protection Sys (RPS) Bus Inadvertently Deenergized,Resulting in Full RPS Actuation. Caused by Personnel Error W/Contributing Factor of Poor Human Factors Design.Info Tag Installed on Power Switch ML19325D1591989-10-13013 October 1989 LER 89-026-00:on 890913,reactor Thermal Power Level Exceeded That Specified in OL Due to Unexpected Recirculation Sys Flow Control Transient.Caused by Component Failure.Failed Isolation Solenoid Valve Replaced ML19325D9331987-03-27027 March 1987 LER 87-010-00:on 870228,operators Failed to Place at Least One Reactor Protection Sys Trip Sys in Tripped Condition within 1 H.Caused by Personnel Error & Deficient Procedure. Personnel Counseled & Procedures Revised ML19325C1171987-03-27027 March 1987 LER 87-009-00:on 870227,failure of Two Control Air Solenoid Valves Rendered Div I & II Diesel Generators Inoperable. Cause Unknown.Solenoid Valves Replaced & Plant Administrative Procedure PAP-1705 revised.W/870327 Ltr 1994-08-10
[Table view] Category:RO)
MONTHYEARML18011A5401994-08-10010 August 1994 LER 94-017-00:on 940711,automatic Isolation of RHR Sys Shutdown Cooling Suction Outboard Containment Isolation Valve Occurred Due to Inadequate Work Order.Work Order Process for I&C Work Orders Will Be reviewed.W/940810 Ltr ML20046C5721993-08-0606 August 1993 LER 93-015-00:on 930709,unexpected RRP Fast to Slow Speed Downshift Occurred Due to Failure of Both RRP Suction Temp Rtd.Replaced & Returned RTD to Mfg for Failure Analysis. W/930806 Ltr ML20046B7811993-08-0202 August 1993 LER 93-014-00:on 930703,TS 3.0.3 Entered Due to Failure of Racs Power Supply.Replaced 5 Volt Power Supply in Racs cabinet.W/930802 Ltr ML20045G7201993-07-0808 July 1993 LER 93-013-00:on 930608,control Room HVAC Sys Train a Supply Fan Tripped on Overcurrent,Resulting in Both Sys Trains Being Unavailable.Caused by Motor Winding Insulation Failure.Motor Repaired by mfg.W/930708 Ltr ML20045G2171993-07-0707 July 1993 LER 93-012-00:on 930607,noted That HPCS Initiation Signal Resulted in Auto Start of Div 3 DG & ESW Sys.Caused by Failure of Div 3 Reserve Battery Charger.Procedures Used for Insp & Maint of Battery Being modified.W/930707 Ltr ML20044F2161993-05-19019 May 1993 LER 93-011-00:on 930419,identified That Excessive Strainer Differential Pressure Across RHR Suction Strainers Could Have Compromised Long Term Cooling During LOCA Operation. Caused by Inadequate Program requirements.W/930519 Ltr ML20044B6771993-02-22022 February 1993 LER 93-004-00:on 930121,MOV Testing of Main Steam Line Drain & Bypass Outboard Isolation Valve Indicated That Thrust Less than Design Thrust to Close Valve Under Accident Conditions. Review,Per GL 89-10 in progress.W/930222 Ltr ML20029B6431991-03-0808 March 1991 LER 91-007-00:on 910209,pressure Switch Instrument Drift Caused Automatic Start of Annulus Exhaust Gas Treatment Sys. Caused by Component Failure.Switch Recalibrated to Adjust Setpoints to Proper value.W/910308 Ltr ML20029B0971991-03-0101 March 1991 LER 91-006-00:on 910202,inboard Isolation Valves Closed on RWCU Delta Flow High Signal During Removal of RWCU Filter from Svc.Caused by Personnel Error.Sys Operating Instruction Being revised.W/910301 Ltr ML20029A6451991-02-22022 February 1991 LER 91-005-00:on 910129,discovered That Two Power Supplies Had Excessive Ripple Effect When All Rods Pushbutton Depressed,Resulting in Loss of Scram Accumulator Fault Indication.Caused by Personnel error.W/910222 Ltr ML20029A3321991-02-15015 February 1991 LER 91-004-00:on 910120,three Reactor Water level-high (Level 8) Channels Inoperable Due to Blown Fuse.Caused by Voltage Spike.Circuitry Associated W/Trip Relays Modified. W/910215 Ltr ML20028H7521991-01-25025 January 1991 LER 90-041-00:between 901212 & 28,inoperable Reactor Pressure Vessel Level Instrumentation Channels Resulted in HPCS Sys Being Inoperable & in Tech Spec Violation.Caused by Personnel Error.Memo issued.W/910125 Ltr ML20024F7421990-12-14014 December 1990 LER 90-033-00:on 901120,Train B of Control Room HVAC Sys Actuated Unexpectedly in Emergency Recirculation Mode.Caused by Inadequate Instruction.Procedure Revised Re Correct Guidance During Loss of Power to Bus K-1-N ML20024F7411990-12-14014 December 1990 LER 90-032-00:on 901116,disconnecting Wires to Test Relay Contact Resulted in RHR a Shutdown Cooling Sys Isolation. Caused by Procedure Deficiency & Inadequate Instructions. Personnel Trained Re Review of Work Orders ML20028G9181990-09-28028 September 1990 LER 90-020-00:on 900831,maint Activities on Control Room Emergency Recirculation Sys Resulted in Tech Spec Violation & Compromise of Safety Sys.Caused by Program Deficiency. Maint Acitivities & Insp Being revised.W/900928 Ltr ML20044B1021990-07-13013 July 1990 LER 90-013-00:on 900619,discovered That Main Steam Line Radiation Monitor C Inoperable for Greater than Time Allowed by Tech Specs 3.3.1.a & 3.3.1.b.Caused by Personnel Error. Personnel counseled.W/900713 Ltr ML20043H4801990-06-20020 June 1990 LER 90-011-00:on 900521,discovered That Divisional LPCI & LPCS Sys Inoperable in Excess of Tech Spec Action Limits Between 871119-23 & 891218-22.Caused by Procedural Deficiency.Sys Operating Instruction revised.W/900620 Ltr ML20043H5251990-06-20020 June 1990 LER 90-010-00:on 900521,Tech Spec Action Requirements Not Implemented for Inoperable Control Rod Scram Accumulators. Caused by Inadequate Procedures & Malfunctioning Transformer.Analyzer Reset & Leakage monitored.W/900620 Ltr ML20043H3841990-06-18018 June 1990 LER 90-009-00:on 900517,RHR Sys B HX Bypass Valve Failed to Reposition on Demand,Rendering RHR Sys Train Operable for Containment Spray Cooling Mode of Operation.Caused by Failure of Valve Stem Nut.Stem Nut replaced.W/900618 Ltr ML20043E5711990-06-0808 June 1990 LER 89-030-01:on 891125,plant Entered Tech Spec 3.0.3 Due to Two Untrippable Control Rods.Failure of Two Control Rods Caused by Improper Seat Matl in Associated Scram Pilot Solenoid Valves.Instructions revised.W/900608 Ltr ML20043A7801990-05-18018 May 1990 LER 90-007-00:on 900418,ruptured Seal on Outer Door of Upper Containment Airlock Occurred Causing Loss of Containment Integrity.Caused by Inadequate Communications & Equipment Failure.Seal on Outer Door Replaced ML20043A8451990-05-18018 May 1990 LER 90-008-00:on 900420,unexpected Isolation of RWCU Sys Occurred.Caused by Component Failure.Faulty Transmitter Transmitter Identified & Replaced ML20042G7731990-05-11011 May 1990 LER 90-006-00:on 900411,control Room Emergency Recirculation Sys Found to Be Inoperable & Tech Specs 3.0.3 Entered on Three Occasions.Caused by Operator Error & Component Failure,Respectively.Personnel retrained.W/900511 Ltr ML20012D8151990-03-24024 March 1990 LER 90-003-00:on 900222 & 23,discovered That Stroke Time Measurements Not Performed in Both Directions for motor- Operated Valves in safety-related Sys.Caused by Program Deficiency.Procedural Enhancement implemented.W/900323 Ltr ML20011E1861990-02-0202 February 1990 LER 90-001-00:on 900107,reactor Scram Occurred After Improper Transfer of 480-volt Ac Power Supplies Resulted in Total Loss of Feedwater Flow & Power Interruption.Caused by Personnel Error.Operator Counseled & Instructions Revised ML20011E1871990-02-0202 February 1990 LER 90-002-00:on 900107,RCIC Sys Isolated Due to High Differential Temp Signal Detected Across RCIC Room Cooler Following Reactor Scram Due to Loss of Feedwater Flow. Caused by Design Deficiency.Procedures Re Flow Rate Revised ML19354E0961990-01-19019 January 1990 LER 89-032-00:on 891228 & 900105,HPCS Sys Declared Inoperable Due to Inoperability of Div 3 Battery.Caused by Low Pilot Cell Voltage,Cell W/Slow Electrolyte Leak & Blown Power Fuse.Fuse & Hydromotor Pump replaced.W/900119 Ltr ML20005E6851990-01-0505 January 1990 LER 89-031-00:on 891206,08 & 15,RWCU Sys Isolations Occurred.Caused by Design Deficiency & Deficiency in Leak Detection/Differential Flow Circuitry Setpoint &/Or Time Delay.Leak Detection Thermocouples relocated.W/900105 Ltr ML20005E0821989-12-26026 December 1989 LER 89-030-00:on 891125,plant Entered Tech Spec 3.0.3 Due to Two Untrippable Control Rods.Caused by Failure to Return Scram Pilot Valves Used for Rods to Mfg After Recall. Surveillance Instruction revised.W/891226 Ltr ML19354D5991989-12-17017 December 1989 LER 89-029-00:on 891117,heater Bay/Turbine Bldg Vent Gaseous Effluent Particulate & Iodine Samples Not Continuously Collected as Required by Tech Spec 3.3.7.10.Caused by Procedure Deficiency.Procedure revised.W/891217 Ltr ML19325E5901989-11-0303 November 1989 LER 89-028-00:on 891008,concluded That Operation of Fuel Pool Cooling & Cleanup Sys to Upper Containment Pools Caused Containment Vacuum Breaker Actuations.Caused by Unrecognized Sys Interaction.Operating Instruction revised.W/891103 Ltr ML19324B1241989-10-27027 October 1989 LER 89-024-01:on 890723,entry Into Operational Condition 2 Completed W/Suppression Pool Makeup Sys Inoperable & on 890725,vent Valve on Ref Leg Found Open & Uncapped.Caused by Personnel Error.Personnel counseled.W/891027 Ltr ML19325D5121989-10-20020 October 1989 LER 89-027-00:on 890925,loss of Control Power to Emergency Svc Water Sys Pump Discharge Valve a Rendered Sys Inoperable.Caused by Personnel Error Re Jumper Placement. Involved Technicians counseled.W/891020 Ltr ML19325D1581989-10-13013 October 1989 LER 88-025-01:on 880618,reactor Protection Sys (RPS) Bus Inadvertently Deenergized,Resulting in Full RPS Actuation. Caused by Personnel Error W/Contributing Factor of Poor Human Factors Design.Info Tag Installed on Power Switch ML19325D1591989-10-13013 October 1989 LER 89-026-00:on 890913,reactor Thermal Power Level Exceeded That Specified in OL Due to Unexpected Recirculation Sys Flow Control Transient.Caused by Component Failure.Failed Isolation Solenoid Valve Replaced ML19325D9331987-03-27027 March 1987 LER 87-010-00:on 870228,operators Failed to Place at Least One Reactor Protection Sys Trip Sys in Tripped Condition within 1 H.Caused by Personnel Error & Deficient Procedure. Personnel Counseled & Procedures Revised ML19325C1171987-03-27027 March 1987 LER 87-009-00:on 870227,failure of Two Control Air Solenoid Valves Rendered Div I & II Diesel Generators Inoperable. Cause Unknown.Solenoid Valves Replaced & Plant Administrative Procedure PAP-1705 revised.W/870327 Ltr 1994-08-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With NUREG-1482, SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant1999-08-0909 August 1999 SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With ML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application PY-CEI-NRR-2409, Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2393, Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored1999-05-12012 May 1999 Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp PY-CEI-NRR-2399, Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected PY-CEI-NRR-2389, Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 PY-CEI-NRR-2369, Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 9902271999-03-0303 March 1999 Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 990227 PY-CEI-NRR-2372, Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 PY-CEI-NRR-2356, Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2346, Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position PY-CEI-NRR-2335, Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2329, Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With ML20153B8221998-09-16016 September 1998 Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A PY-CEI-NRR-2323, Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2313, Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2306, Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 1 ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted PY-CEI-NRR-2282, Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 PY-CEI-NRR-2277, Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20216J1401998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2258, Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 1 1999-09-30
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- l l At 0107 on April 18, 1990, a seal on the outer door of the Upper Containment Airlock ruptured, while the inner door was opened, resulting in violation of Technical Specification 3.6.1.3 and a loss of containment integrity being declared for a total of approximately two minutes. At the time of the event, a Chemistry Technician was entering containment to obtain samples. Inadequate communications between the control room and the technician resulted in the technician using the inner door again causing two more losses of containment integrity.
The cause of this event was equipment failure. The small seal on the outer door ruptured causing the outer door to become inoperable, resulting in a loss of containment integrity when the inner door was opened. Additionally, personnel errors (inadequate knowledge / training and inadequate communication) were responsible for the second and third loss of containment integrity.
To prevent recurrence, the small seal on the outer door of the Upper Containment Airlock was replaced and an engineering evaluation is being performed to determine what caused the seal failure. Radiological Controls Training for people who operate the airlock doors is being enhanced co explain the consequences of improper operation of airlock doors and signs are being posted inside the containment airlocks to provide additional operating instructions. The event was discussed with the operator who is fully aware of the impact that inadequate communication had on this event. Uditionally, as part of the established requalification training program, all pint. licensed operators vill be instructed on the lessons learned from thic tvent.
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o l ol 7 - ojo ol9 M o l3 text ,, . < . ac w anw.nm t At 0107 on April 18, 1990, a seal [ SEAL) on the outer door of the Upper "
Containment [NH] Airlock [AL) ruptured, while the inner door was opened, resulting in violat).cn of Technical Specification 3.6.1.3 and a loss of
- containment integrity being declared for a total of approximately two minutes.
l At the time of the event, the plant was in Operational Condition 1 (Power Operation) at approximately 100 percent of rated thermal power with the Reactor 1 l
Pressure Vessel [RPV} at saturated conditions at approximately 1013 psig.
At 0107 on April 18, 1990, a Chemistry Technician entered containment, to obtain samples, using the Upper Containment Airlock. At the time of the event, the Lower Containment Airlock was inoperable due to' maintenance. The technician entered through the outer door, using manual operation of the Airlock, and saw I l the proper indications, after closing the outer door, to open the inner door.
j When the technician opened the inter door, the control room received an alarm and I indications that both the inner and outer airlock doors were open at the same time. (Outer door small seal low pressure occurring with the opening of the inner door caused the alarm and indications). Additionally,' the technician in the airlock noted that the outer door no longer indicated closed. The control room operator contacted the technician and, not realizing that the technician was inside containment, gave instructions which resulted in the technician exiting ,
containment via the inner door (which again caused the alarm in the control room) l l to manually open and close the outer door in anticipation of clearing the ,
problem. After closing the inner door, the technician opened and closed the '
i outer door but could not clear the open indications. The technician then 4 re-entered containment through the inner door (again causing the alarm in the l control room). Upon closing the inner door and contacting the control room to inform them that the outer door problem had not cleared, the technician was instructed to remain in containment until one of the airlocks became operable.
The technician exited containment via the Lower Containment Airlock after the .
Lower Containment Airlock was declared operable at approximately 0530 on April r 18, 1990. Subsequently, the small seal on the outer door of the Upper Containment Airlock was replaced and the Upper Containment Airlock was declared operable at 0835 on April 21, 1990.
The cause of this event was equipment failure. The small seal on the outer door' [
ruptured (a rip approximately three eighths of an inch long) causing the outer door to become inopera).e and a loss of containment integrity when the inner door was opened. Additionally, personnel errors, inadequate knowledge / training and inadequate communication, were responsible for the second and third loss of containment integrity. Once problems with the outer door were' suspected, the inner door should not have been reopened until the outer door was repaired. The manual cycling of the door should have been accomplished by someone outside of containment. This would have eliminated the last two openings of the inner door ,
and reduced the risk of extended loss of containment integrity had the inner. door i malfunctioned while being operated. The control room operator did not establish the exact location of the Chemistry Technician prior to instructing him to ';
manually cycle the outer door and the Chemistry Technician operated the airlock doors without the doors indicating proper conditions for operation. ,
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olo nl1 0F n lg itrT rn a a== een r. amamaw anc s Janaw nri The personnel airlocks are wolded steel assemblies with double doors, each equipped with double gaskets or seals. The airlocks are designed so that pressure inside the containment would aid in positively seating the door assemblies. Only one closed door in each airlock is required to maintain the integrity of the containment. During this event, the inner door of~one airlock was opened for a total of approximately two minutes while the outer door was inoperable. Technical Specification 3.6.1.3 contains a footnote which allows passage into and out of containment during power operation for up to I hour .
(cumulative) per year to repair an inoperable inner airlock door. Although this allowance did not specifically permit the sequence of events which occurred on April 18,1990, its bases would bound any resulting effects on safe plant-operation. Additionally, the large seal on the outer door continued to function properly during this event. As a result, no direct communication'between the inside and outside of containment was possible, even though-Technical Specifications required the outer door to be declared inoperabic. Therefore, this event is not considered to be safety significant. Previous Licensee Event Reports have been submitted because of problems with: containment airlocks. LER 87-061 addressed a problem with locking pins, LER 88-032 addressed problems with 3-way ball valves and a blistered seal, and LER 88-035 addressed a mechanical interlock failure. However, the recent failure nechanism has not been experienced before, and none of the corrective actions f rom previous LERs could have been expected to prevent this event. -
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, To prevent recurrence, the small seal on the outer door of the Upper Containment l Airlock was replaced and an engineering evaluation is being performed to dete rminst what caused the seal failure. Radiological Controls Training for i people who operate the airlock doors is being enhanced to explain the -
consequences'of improper operation of airlock doors and signs are being~ posted inside the containment airlocks to provide additional operating instructions.
The event was discussed with tne operator who is fully aware of the impact that
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L inadequate communication had on this event. Additionally, as part of the established requalification training program, all plant licensed operators will be instructed on the lessons learned from this event.
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Energy Industry Identification System codes are identified in the text as [XX].
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